| FUEL PIN MELTING IN A FAST REACTOR AND MELT SOLIDIFICATION: SIMULATION USING THE SAFR/V1 MODULE OF THE EVKLID/V2 INTEGRAL CODE |
4 |
| Nuclear Problems of Thermonuclear Power Generation |
3 |
| SAFR/V1 (EVKLID/V2 Integral Code Module) Aided Simulation of Melt Movement Along the Surface of a Fuel Element in a Fast Reactor During a Serious Accident |
2 |
| Purification of Regenerated Uranium Hexafluoride by Removal of U-U-U-236 in the Intermediate Product of a Two-Feed-Flow Cascade |
2 |
| Radiolysis of U-U-234-Enriched Regenerated-Uranium Hexafluoride at the Temporary Storage Stage in a Separation Plant |
2 |
| Neptunium-Based High-Flux Pulsed Research Reactor |
2 |
| MECHANISM OF CHANGE IN VVER--1000 VESSEL MATERIAL PROPERTIES IN IRRADIATION-RECOVERY ANNEALING-IRRADIATION CYCLE |
2 |
| Possibility of Increasing the Number of Experimental Channels in VVR-Ts by Changing the Core Design |
1 |
| Economic Efficiency of Bringing Depleted Uranium into Enrichment |
1 |
| MODERATE-BREEDING FAST REACTORS AND THE STRUCTURE OF NUCLEAR POWER |
1 |
| EVALUATION OF SOKRAT CODE POSSIBILITY TO MODEL URANIUM-DIOXIDE FUEL DISSOLUTION BY MOLTEN ZIRCONIUM |
1 |
| Effect of Cellular Lattices, Heat-Exchange Intensifiers, and Coolant Mixing on the Critical Power of VVER FA |
1 |
| Cocrystallization of Uranyl and Plutonyl Nitrate Hexahydrates |
1 |
| Americium Utilization Via Pyroelectrochemical Granulation and Vibrocompaction Technologies |
1 |
| Irradiated FA Structural Materials Conditioning by Induction-Slag Remelting in a Cold Crucible |
1 |
| Experiment-Based Verification of the SAFR/V1 Module of the EVKLID/V2 Integral Code for Thermal Breakdown of Fuel Pins in a Fast Reactor |
1 |
| Radiation Risk and Features of Its Perception |
1 |
| Water Supply System with Light-Water Production Based on a Nuclear Desalination Complex |
1 |
| Effect of Deformation on the Temperature Regime in Fast-Reactor Cores |
1 |
| Characteristics of Heat Transfer During Boiling of Liquid Metal in the Fuel Assemblies of Fast Reactors in Emergency Regimes |
1 |
| Management of Spent Nuclear Fuel from Research Reactors at the Kurchatov Institute |
1 |
| Impact of the Precipitation of Boric Acid and its Salts on the Operability of Passive Safety Systems During Serious Accidents in NPP |
1 |
| Conditions and Initial Data for Reconstructing the Environmental Radioactive Contamination and Population Dose Loads Resulting from a Nuclear Accident on a Nuclear Submarine in Bukhta Chazhma |
1 |
| Pu-239-Be-Source Based Neutron Reference Fields |
1 |
| Method of Determining the Reliability of Real-Time In-reactor Monitoring of VVER |
1 |
| RESULTS OF INVESTIGATIONS OF BREST-TYPE REACTOR FUEL RODS WITH MIXED URANIUM-PLUTONIUM NITRIDE FUEL, IRRADIATED IN BOR-60 AND BN-600 |
1 |
| Swelling of Uranium Dioxide-Silumin Dispersion Fuel Composition in Experimental Fuel Elements of the SM Reactor |
1 |
| Testing of an Integrated Nitrogen Oxide Catcher |
1 |
| Study of the Long-Term Strength of Neutron-Irradiated Austenitic and Ferrite-Martensite Steel |
1 |
| Methanol Production Based on Direct-Flow Gas Generator and Nuclear Reactor |
1 |
| DEVELOPMENT OF A RADIOTHERAPY SYSTEM BASED ON 6 MeV LINAC AND CONE-BEAM COMPUTER TOMOGRAPH |
1 |
| Neutronics Model of the IVG.1M Reactor: Development and Critical-State Verification |
1 |
| Investigation of the Influence of the Magnetic Field of a Well on the Neutron Tube of a Geophysical Apparatus |
1 |
| Np, Am, Cm Transmutation in Different Types of Reactors |
1 |
| LiF-NaF-KF Eutectic Based Fast Molten-Salt Reactor as Np, Am, Cm Transmuter |
1 |
| Coolant Mixing Intensity and Hydraulic Resistance of FA Mixing Grids |
1 |
| HEAT-AND-MASS TRANSFER INTENSIFICATION IN SATURATED-STEAM GENERATORS IN NPP WITH VVER AS A MEANS FOR INCREASING EFFICIENCY AND RELIABILITY |
1 |
| AEROSOL-LM/Na Aided Simulation of Fission Product Production and Transport in the First Loop of a Fast Reactor |
1 |
| NEUTRON GAMMA-METHOD FOR MONITORING ASH CONTENT OF COAL |
1 |
| USE OF HIGH-FREQUENCY FIELDS FOR CENTRIFUGAL SEPARATION OF SPENT NUCLEAR FUEL |
1 |
| Dynamics of Power Pulses in a Research Reactor with Neptunium Nuclear Fuel |
1 |
| Investigation of Transient Xenon Processes in VVER-1200 at the Novovoronezh NPP |
1 |
| RBMK Uranium-Erbium Fuel |
1 |
| Reactivity Runaway Reduction When Using Enriched Uranium in a Lead Fast Reactor |
0 |
| Neutronics Calculation of Fast Reactor Using Modern Computing Systems |
0 |
| Mathematical Model for Evaluating the Technical Condition and Predicting Collapse of Protective Barriers on Flooded Radiation-Hazardous Sites |
0 |
| Effect of the Principle of Radiation Protection Optimization on Radwaste Management Technology |
0 |
| STRUCTURE OF THE PUBLIC IRRADIATION DOSE DURING OPERATION OF EXPERIMENTAL-DEMONSTRATION POWER COMPLEX ENTERPRISES |
0 |
| Accounting for Environmental Aspects in Water-Chemistry Optimization of the Second Loop of NPP with VVER |
0 |
| OPTIMIZATION OF THE RADIATION PARAMETERS ON TECHNOLOGICAL INSTALLATIONS |
0 |
